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Uwaba, Tomoyuki
JNC TN9420 2000-005, 28 Pages, 2000/03
JNC-TN9420-2000-005.pdf:0.94MB
In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO
, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.
gas cooled reactor; ; Mizuta, Shunji
JNC TN9400 2000-040, 41 Pages, 2000/03
JNC-TN9400-2000-040.pdf:0.85MB
The corrosion behavior of ferritic stainless steels applied to core components under C0 gas environment was investigated in order to be helpful to fuel design in C0 gas cooled reactor as the feasibility study for fast breeder reactor. The dependence of the corrosion behavior, before a breakaway occurs, on C0 gas temperature, Si and Cr contents of ferritic steels was determined quantitatively. The following correlations to calculate the metal loss thickness was established. X = 4.4w w = √(k
t) k = 
exp( - 5.45[Si]) exp( - 1.09[Cr]) exp( - 11253/T) = 1.65 10
4.40 10
X : metal loss thickness[
ml, w : corrosion weight gain [mg/cm
] k : parabola constant [(mg/cm)/hr], t : time [hr], : constant [Si] : Si content[wt.%], [Cr] : Cr content [wt.%], T : temperature [K]
*; Kitada, Takanori*; Tagawa, Akihiro; *; Takeda, Toshikazu*
JNC TJ9400 2000-006, 272 Pages, 2000/02
JNC-TJ9400-2000-006.pdf:9.69MB
Investigation was made on the follwing three themes as a part of the improvement of reactor physics analysis method for FBR with various core concept. Part 1: Investigation of Error Estimation of Neutron Spectra in FBR and Suggestions to Improve the Accuracy. In order to improve the spectrum unfolding method used in fast experimental reactor JOYO, a trial was made to evaluate the error in the estimated neutron spectrum, cause by cause. And the evaluated errors were summed up to obtain the most probable and reasonable error as possible. The summed up error was found relatively small compared to the error caused by the uncertainty of cross section data: most of the error in the spectrum unfolding method can be attributed to the error in cross sections. It was also found that the error due to the fission spectrum causes a considerable error in the high energy neutron spectrum which is over several MeV. Part 2: Study on Reactor Physics Analysis Method for Gas-Cooled FBR. In gas-cooled FBR, the portion of coolant channels in core volume is larger than sodium-cooled FBR. This leads to strong neutron streaming effects. For sodium-cooled FBR, several methods were proposed to evaluate the neutron streaming effect, however, these methods can not be used directly to gas-cooled reactor because the direction dependent diffusion coefficient becomes infinitive along the direction pararel to the coolant chammel. In this study, a new method is proposed to evaluate the neutron streaming effect, based on the method taking the axial buckling into consideration, which method was originally proposed by K
hler. Part 3: Study on Reactor Physics Analysis Method for Water-Cooled FBR An investigation was made on low-moderated water-cooled FBR, on the point that the ordinary used analysis method for FBR may give considerable difference in results in such core. In light water reactors, it is well known that the space dependence of self-shielding effect of heavy nuclides are considerably ...
Shimomura, Hiroaki; Kawaji, Satoshi; Fujisaki, Katsuo;
JAERI-M 89-064, 90 Pages, 1989/06
no abstracts in English
Ogawa, Masuro
Int.J.Heat Mass Transfer, 30(5), p.1017 - 1026, 1987/05
Times Cited Count：5 Percentile：52.63(Thermodynamics)no abstracts in English
Ogawa, Masuro
Nihon Kikai Gakkai Rombunshu, B, 53(488), p.1351 - 1359, 1987/00
no abstracts in English
; ;
High Temperatures-High Pressures, 15, p.707 - 714, 1983/00
no abstracts in English
; ; ; ;
JAERI-M 9153, 31 Pages, 1980/10
no abstracts in English
Sanokawa, Konomo; Ouchi, Mitsuo;
Nihon Genshiryoku Gakkai-Shi, 22(2), p.121 - 128, 1980/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
; Sanokawa, Konomo; Ouchi, Mitsuo; Takizuka, Takakazu; Nekoya, Shinichi; Ogawa, Masuro; Emori, Kouichi
Nihon Genshiryoku Gakkai-Shi, 22(4), p.251 - 263, 1980/00
Times Cited Count：3 Percentile：41.98(Nuclear Science & Technology)no abstracts in English
; Nekoya, Shinichi; Emori, Kouichi; Ogawa, Masuro; Ouchi, Mitsuo; Okamoto, Yoshizo; Sanokawa, Konomo; *; *; *; et al.
Nihon Genshiryoku Gakkai-Shi, 22(3), p.181 - 188, 1980/00
Times Cited Count：1 Percentile：22.79(Nuclear Science & Technology)no abstracts in English
JAERI-M 7844, 218 Pages, 1978/10
no abstracts in English
*; Okamoto, Yoshizo
JAERI-M 7214, 54 Pages, 1977/08
no abstracts in English
; Tagawa, Hiroaki; ; ; Ono, Shinichi;
JAERI-M 5642, 69 Pages, 1974/03
no abstracts in English
Okamoto, Yoshizo; Sanokawa, Konomo; ; ; Akino, Norio;
JAERI-M 5152, 17 Pages, 1973/03
no abstracts in English
*; ; *; Okamoto, Yoshizo
Int.Chem.Eng., 13(3), p.546 - 552, 1973/03
no abstracts in English
Nihon Kinzoku Gakkai Kaiho, 12(3), p.181 - 187, 1973/03
no abstracts in English
*; *; ; *
FAPIG, (69), p.2 - 7, 1973/00
no abstracts in English
;
Nihon Genshiryoku Gakkai-Shi, 13(8), p.456 - 461, 1972/00
no abstracts in English
